ML20237J616
| ML20237J616 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/31/1987 |
| From: | Crawford J, Robert Lewis TENNESSEE VALLEY AUTHORITY |
| To: | NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 0487K, 487K, NUDOCS 8708180257 | |
| Download: ML20237J616 (17) | |
Text
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, TENNESSEE VALLEY AUTHORITY 0FFICE OF NUCLEAR POWER I-i BROWNS FERRY NUCLEAR PLANT l'
l MONTHLY OPERATING REPORT TO NRC JULY 1, 1987 - JULY 31, 1987 I
DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE. NUMBERS.DPR-33, DPR-52, AND DPR-68 Submitted by:
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f CONTENTS 1
Operations' Summary.
Refueling Information....
3 5
.Significant Operational Events..
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Operating Data Report........ -........ *..........
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Average Daily. Unit Power Level.
' Unit Shutdowns and Power Reductions.
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r Operations Summary JULY 1987 The following summary describes the significant operation activities during the reporting period.
In support of this summary, a chronological log of significant events is included in this report.
There was one reportabic occurrence and no revisions to previous occurrences reported to NRC during the month.
Unit 1 The unit remained on administrative hold the entire month. The unit is also undergoing its end-of-cycle 6 refueling.
Unit 2 The unit remained on administrative hold the entire month. The unit is also undergoing its end-of-cycle 5 refueling.
Unit 3 The unit remained on administrative hold the entire month. The unit is also undergoing environmental qualifications to comply with NRC requirements.
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j Operations Summary (Continued)
JULY 1987 1
Fatigue Usame Evaluation I
The cumulative usage' factors for the reactor vessel,are as follows:
Location Usage Factor Unit 1 Unit 2 Unit 3 1
Shell at water line 0.00620 0.00492 0.00430 l
Feedwater nozzle 0.29782 0.21319 0.16133 Closure studs 0.24204 0.17629
- 0.14326-NOTE: 'This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.b(3) reporting requirements..
Common System Approximately 1.03E+06 gallons of waste lie ':ds were discharged containing approximately 2.65E-02 curies of activity.
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l Atfuelinr. Information JULY 1987 Unit 1 j
Unit 1 was placed on administrative hold in March 1985 to resolve TVA and NRC concerns. The uadt also began its sixth refueling on June 1, 1985, with a scheduled restart date to be determined. The sie.th refuell'ng will involve loading 8x8R (retrofit) fuel assemblies into the core.
The prior-to-startup unit 1 items are environmental qualification of electrical equipment (10CFR50.49), torus modification (NUREG 0661), containment modifications (NUREG 0737), electrical changes,(Appendix R 10CF350p (all), MSIV modifications, modification of masonry walls (IEb'80-11), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modification i(Appendix J), HPCI concerns, modification of PCIS logic (LER 259/85009), replacement of plant process computers, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG 0737), RpS modifications (IE Notice 78-45), H 0 sample line modification (LER 81050), radiation monitors modification (LER 80033), EECW carbon to stainless pipe change out, and all NRC commitment items except Anticipated Transients Without Scram (ATWS) modifications which are scheduled for next outage.
There are 0 assemblies in the reactor vessel. The spent fuel storage pool presently contains 284 new assemblies, 764 EOC-6, 252 EOC-5, 260 EOC-4, 232 EOC-3, 156 EOC-2, and 168 EOC-1 assemblies. The present available cap 6 city
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of the fuel pool is 1355 locations.
Unit 2 Unit 2 was shut down on September 15, 1984, for its fifth refueling outage with a scheduled restart date to be determined. On September 3, 1985, the unit Iwas plac'ed on administrative hold to resolve TVA and 4RC safety concerns. The
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fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core.
The prior-to-startup unit 2 items are CRD SDIV piping modification (IEB 80-17),
environmental qualification of electrical equipment (10CFR50.49), torus modifications (NUREG 0661), containment mo(ification (NUREG 0737), electrical changes (Appendix R 10CFR50) (partial), MSIV modifications, modification of masonry walls (IEB 80-11), addition of feedwater nozzle temperature monitoring (NUREG 0619), evaltation of the vent drain and test connections, VDTC, (LER 82020), valve modification (Appendix J) (partial), D/G rpeed sensor i
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Refuelinr. Information g.
JULY 1987 Unit 2 (Continued)
' installation (LER 81004), HPCI and RCIC testable check valve change out, modification of PCIS logic (LER 259/85009), HPCI concerns, seismic program review, and EECW carbon to stainless pipe change out.
There are 0 assemblies in the reactor vessel. At month end there were 304 new assemblies, 764 EOC-5, 248 EOC-4, 352 EOC-3, 156 EOC-2, and 132 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 1481 locations. All HDRs have been installed in the pool-l with the exception of two.
Unit 3 Unit 3 was shut down on March 9, 1985, and placed on administrative hold to resolve various TVA and NRC concerns with a scheduled restart date to be determined. The sixth refueling outage has been scheduled for September 21, 1988, and involves loading 8x8R (retrofit) assemblies into the core and ATWS modifications. The prior-to-startup unit 3 items are environmental qualifica-tion of electrical equipment (10CFR50.49), containment modifications (NUREG 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifica-
'tions, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modifications (Appendix J), HPCI concerns, replacement of plant process computer, seismic qualifications of piping <(CEB'79-02/14), postaccident evaluation (NUREG 0737), addition of redundant drywell control air supply, RPS modification (IE Notice 78-45),
2 2 8'.4mple line niodification (LER 81050), radiation monitor modification H0 (LER 80033), replacement of jet pump holddown beam assemblies (IEB 80-07),
change out of suitches in SBGT (LER 83018), EECW carbon to stainless pipe change out, and plant design upgrade to seismic qualification.
l l
There are 0 assemblies in the reactor vessel. There are 764 assemblies to finish cycle 6, 248 EOC-5, 280 EOC-4, 124 EOC-3, 144 EOC-?, and 208 EOC-1
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assemblies in the spent fuel storage pool. The present available capacity of
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l the fuel pool is 585 locations. All high density racks 0:DR) have been
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installed in the pool with the exception of six.
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Significant Operational Events JULY 1987 i
Unit 1 07/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and i
modifications continues.
07/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.
Unit 1 07/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and l
modifications continues.
i 07/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.
Unit 3 07/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
07/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
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I OPERATING DATA REPORT DOCKET NO. 50-259 DATE 8-1-87 COMPLETED BY T.
- n. crawford TELEPHONE -(205) 729-2507 OPERATING STATUS
- 1. Unit Name:
Browns Ferry Unit One Notes 2 :leporting Period:
July 1987
- 3. Licensed Thennal Power IMht):
3293 4.' Nameplate Rating (Gross MWe):
1152
- 5. Design Electrical Rating (Net MWe): 1M
- 6. Maximum Dependable Capacity (Gross MWe):
1098.4
- 7. Maximum Dependable Capacity (Net MWe):
1065
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7)Since Last Report.Give Reasons:
- 9. Power Level To which Restricted. if Any (Net MWe):
N/A
- 10. Reasons For Restrictions,if Any:
N/A N/A This Month Yr..t o-Date Cumulative i1. Hours in Reporting Period 744 5087 114,007
- 12. Number Of Hours Reactor Was Critical 0
0 59,521.38
- 13. Reactor Reserve Shutdown flours 0
0 6,997.44
- 14. Hours Generator On-Line 0
0~
58.267.26
- 15. Unit Reserve Shutdown flours 0
0 0
- 16. Gross Thermal Evergy Generated (MWH) 0 0
168,066,787 17 Gross Electrical Energy Generated (MWill 0
0 55,398,130
- 18. Net Electrical Energy Generated (MWH)
-758
-10526 53,710,109
- 19. Unit Service Factor 0
0 M.1
- 20. Unit Availability Factor 0
0 51.1
- 21. Unit Capacity Factor (Using MDC Net) 0 0
44.2
- 22. Unit Capacity Factor (Using DER Net) 0 0
44.2
- 23. Unit Forced Outage Rate 100 100 38.9
- 24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date, and Duration of Each t:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
To be determined 2tr Units in Test Status (Prior io Commercial Operationi:
Forecast Achieved INITIA L CRITICALITY 4
1 INITIA L ELECTRICITY COMMERCIAL OPERATION t
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f OPERATING DATA REPORT DOCKET NO.
50-260 DATE 8/1/R7 COMPLETED BY t n_ crauforq TELEPHONE (205) 729-250, OPERATING STATUS 1, Unit Name: Browns Ferry Unit Two Notes
- 2. Reporting Period: July 1987 3293
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross MWe):
1152'
- 5. Desigri Electrical Rating (Net MWe): !065 1098.4
- 6. Maximum Dependable Capacity (Gross MWe):
1065
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
N/A 9 Power Level To which Restricted. lf Any (Net MWe):
N/A
- 10. Reasons For Restrictions.lf Any:
N/A This Month Yr.-to Date Cumulative
- 11. Hours in Reporting Period 744 5087 108894
- 12. Number Of Hours Reactor Was Critical 0.
0 55,860.03 0
0 14.200.44
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On-Line -
0 0
54,338.36
- 15. Unit Reserve Shutdown flours n
n n
- 16. Gross Thermal Energy Generated (MWH) 0 0
153,245,167
- 17. Gross Electrical Energy Generated (MWH) 0 0
50,771,798 18.' Net Electrical Energy Generated (MWH)
-2154
-14745 49,203,558
- 19. Unit Service Factor n
n so.n
- 20. Unit Availability Factor 0
0 50.0
- 21. Unit Capacity Factor (Using MP Net) 0 0
42.4
- 22. Unit Capacity I' actor (Using DER Net) 0 0
42.4 100 100 37.7
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each1:
25, if Shut Down At End Of Report Period. Estimated Date of Startup:
To be determined
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIA L CRITICALITY j
INITIAL ELECTRICITY
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COMMERCI AL OPERATION
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OPERATING DATA REPORT DOCKET NO. 50-296 DATE 8/1/87 COMPLETED BY
_3.
D. Crawford TELEPHONE r9na 790-2507 OPERATING STATUS
- 1. Unit Name:
Browns Ferry Unit Three Notes
- 2. Reporting Period: July 1987
- 3. Licensed Thennal Power (MWt): 3293
- 4. Nameplate Rating (Gross MWe): 1152
- 5. Design Electrical Rat'ing (Net MWe): 1065
- 6. Maximum Dependable Capacity (Gross MWe):
109R 4
- 7. Maximum Dependable Capacity (Net MWe):
1065
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:
N/A
- 9. Power Level To Which Restricted. lf Ary (Net MWe):
N/A
- 10. Reasons For Restrictions. lf Any:
N/A This Month Yr.-to-Date Cumulative
- 11. Hours in Reporting Period 744 5087 91319
- 12. Number Of Hours Reactor Was Critical 0
0 45,306.08
- 13. Reactor Reserse Shutdown Hours 0
0 5,149.55
- 14. Hours Generator On-Line 0
0 44,194.76
- 15. Unit Reserve Shutdown flourr 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
131,868,267
- 17. Gross Electrical Energy Generated (MWH) 0 0
43,473,760
- 18. Net Electrical Energy Generated (MWH)
-5349
-29102 42,063,026
- 19. Unit Service Factor 0
0 48.4
- 20. Unit Availability Factor 0
0 48.4
- 21. Unit Capacity Factor (Using MDC Net 1 0
0 43,2
- 22. Unit Capacity Factor (Using DER Net) 0 0
43.2
- 23. Unit Forced Outage Rate 100 100 40.8
- 24. Shutdowns Scheduled Over Nest 6 Months iType.Date.and Duration of Eacht:
- 25. If Shut Down At End Of Report Period. Estimated Date of Start *:p:
To be determined
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIA L CRITICA LITY INITI AL ELECTRICITY
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-259 UNIT ONE DATE R-1-87 COMPLETED BY J. D. Crawford TELEPHONE (205) 729-2507 MONTH JULY DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL
. (MWe-NeO (MWe Neo
-1 3
17' -1 2
-1 Ig 3
-l gg
_1 4
-1 20
-1
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-1 5
21 6
~
I 22
-1 s
7
-1 23
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-l 8
24
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-1 9
73
.j 10
-l' 26
-1 11
-1 27
-1
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-1 12 28
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13 29 14
-1 30
~1 15 ji
-1 16
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l' INSTRUCTIONS On this forinato list the average daily unit power leselin MWe. Net for each day in the reporting montit. Ctunpuie to the nearest whole megawatt.
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AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260-WO l
UNIT t
l DATE 8-1-87 COMPLETED BY J.'D. Crawford
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TELEPHONE -(205) 729-2507
. SiONTH '
JULY DAY
- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) g ywe. Net t
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-3 17
-3
-3'
-3 2
ig 1
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- -3 4-20
-3 5
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-3 24
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25
-3 1
10 26
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_3 12 2g 13
-3
-4 39 14
-3 30 -2
-3 l
15 3i
~4 16 INSTRUCTIONS
. On this format, list the average daily umt power level in MWe Net for each day in the reportmp month. Compute to i
the nearest whole megawatt.
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. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-296 UNIT. THREE
.DATE 8-1-87 l
COMPLETED BY J. D. Crawford
~ TELEPHONE (205) 729-2507-l..
MONTH JULY 1
DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe.Ne:)
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INSTRUCTIONS On this forrnat list the average daily unit power levelin MWe. Net for each day in the reporting month. Compute to j
the nearest whole megawatt,
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TENNESSEE VALLEY A*JTHORITY Browns Ferry Nuclear Plant
+
1 Post Office Box 2000 Decatur, Alabama 35602 AUG 121987 i
U.S. Nuclear Regulatory Commission ATTN: -Document Control Desk Office of Nuclear Reactor Regulation Washington, D.C.
20555 Attention:
Office of Management Information and Program Control In the Matter of the
)
Docket Nos. 50-259 Tennessee Valley Authority
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50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - MONTHLY OPERATING REPORT - JULY 1987 Enclosed is the July-1987 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.
Very truly yours, TENNESSEE VALLEY AUTHORITY Robert L. Lewis Plant Manager Enclosure cc: Mr. G. E. Gears Mr. G. G. Zech, Director Browns Ferry Project Manager TVA Projects U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue 101 Marietta St., NW, Suite 2900 Bethesda, Maryland 20814 Atlanta, Georgia 30323 U.S. Nuclear Regulatory Commission Browns Ferry Resident Inspector Region II Browns Ferry Nuclear Plant 1
Attn:
Dr. J. Nelson Grace, P.O. Box 311 Regional Adrainistrator Athens, Alabama 35611 101 Marietta Street, NW, suite 2900 J
Atlanta, Georgia 30323 INPO Records Center l
Institute of Nuclear Power Mr. Ted Marston, Director Operations Electric Power Research Institute Suite 1500 P. O. Box 10412 1100 circle 75 Parkway Palo Alto, California 94304 Atlanta, Georgia 30389 V
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l An Equal Opportunity Employer Q
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